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Results for Exercise I-3 with COBAYA: Analysis of the peaking power factors

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Results for Exercise I-3 with COBAYA:

Analysis of the peaking power factors

E. Castro, S. Sánchez-Cervera, N. García-Herranz, D. Cuervo

[email protected]

(2)

Background

Objectives

Methodology

Results of k

eff

Results of power distributions

Results of peaking power factors

Conclusions

(3)

Background

UPM methodology for Uncertainty Quantification is based in two tools:

• SCALE 6.2.1: NEWT and Sampler.

• COBAYA: core simulator with nodal and pin-by-pin capabilities

Random few-group libraries for COBAYA can be generated in an

automatic way using SCALE by stochastic sampling of nuclear data with Sampler(NEWT) → presented in UAM-9

UQ capabilities in COBAYA → presented in UAM-9

• 1st. Order PT (full covariance matrix required)

• Sampled-based (set of random few-group libraries required)

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Objectives

Exercise I-3: UQ in TMI-1 full core calculations using

SCALE(NEWT)/COBAYA at both nodal and pin-by-pin levels

Specific objectives:

• Contribute with updated results to Ex I-3, computing uncertainties in

k-eff, radial power distributions and peak factors.

• Compare nodal and pin-by-pin results.

• Evaluate the probability distribution of core parameters.

TMI-1 ARI core definition: FA Enrichment(w/o) BP(%) Gd (pins)

1 4.00 -

-2 4.95 3.5 4

3 5.00 - 4

4 4.40 -

-5 5.00 3.5 4

6 4.85 - 4

7 4.95 - 4

8 5.00 - 8

9 4.95 - 8

10 4.95 3.5

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-Methodology

SAMPLER / NEWT FA 1

SAMPLER / NEWT FA 2

...

SAMPLER / NEWT FA 27

Perturbed NEMTAB cross section libraries Perturbed COBAYA simulations Perturbed core results NEWT2NEMTAB tool

A sampling-based approach using SCALE and COBAYA was used to

propagate uncertainties in nuclear data to core parameters.

Advantages:

Very easy to implement.

Any kind of observable can be analyzed.

(6)

Methodology

SAMPLER / NEWT FA 1

SAMPLER / NEWT FA 2

...

SAMPLER / NEWT FA 27

Perturbed NEMTAB cross section libraries Perturbed COBAYA simulations Perturbed core results NEWT2NEMTAB tool

NEWT (SCALE 6.2.1) was used as lattice code.

SAMPLER was used to produce perturbed NEWT inputs.

56g-v7.1 cross sections and covariance library.

11 unrodded FA, 7 rodded FA, 1 reflector.

900 random samples for each fuel assembly type:

900 * 19 lattice calculations.

Nodal homogenization.

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Methodology

SAMPLER / NEWT FA 1

SAMPLER / NEWT FA 2

...

SAMPLER / NEWT FA 27

Perturbed NEMTAB cross section libraries Perturbed COBAYA simulations Perturbed core results NEWT2NEMTAB tool

NEWT outputs are grouped together in NEMTAB-formatted libraries:

NEWT2NEMTAB tool.

Parametrized libraries as a function of coolant density, coolant

temperature, fuel temperature and boron concentration.

Nodal library contains 19 materials.

(8)

Methodology

SAMPLER / NEWT FA 1

SAMPLER / NEWT FA 2

...

SAMPLER / NEWT FA 27

Perturbed NEMTAB cross section libraries Perturbed COBAYA simulations Perturbed core results NEWT2NEMTAB tool

COBAYA core simulator:

Solves the multigroup neutron diffusion equation corrected by

interface discontinuity factors.

Nodal solver: Analytic Coarse-Mesh Finit-Difference (ACMFD).

(9)

Methodology

SAMPLER / NEWT FA 1

SAMPLER / NEWT FA 2

...

SAMPLER / NEWT FA 27

Perturbed NEMTAB cross section libraries Perturbed COBAYA simulations Perturbed core results NEWT2NEMTAB tool

A statistical analysis of the 900 core results is performed:

Mean values.

Standard deviations.

Moments of higher order.

Histograms.

(10)

Results of k

eff

k

eff

∆k/k(%)

Nodal

1.00373

0.515

Pin-by-pin

1.00350

0.515

Good agreement between the two solvers.

(11)

Results of k

eff

With 200 samples: 62 pcm difference between the mean and the unperturbed values

Unperturbed (nominal)

value in blue Final relative SD

value in blue

(12)
(13)

Results of peaking power factors

Nodal

Pin-by-pin

F

∆H

node/pin

1.71 (2.1%)

1.91 (2.8%)

F

∆H

assembly

1.64 (0.4%)

1.60 (1.1%)

F

xy

node/pin

2.11 (0.5%)

2.46 (0.7%)

F

xy

assembly

2.05 (0.5%)

2.12 (0.5%)

F

q

node/pin

2.56 (2.3%)

2.74 (2.7%)

F

q

assembly

2.45 (0.5%)

2.30 (1.1%)

• Assembly averaged results can be used to compare both solvers.

• Mean values are consistent between solvers.

• Standard deviations show large differences.

• Are they normally distributed?

𝐹𝐹∆𝐻𝐻 = 𝑃𝑃𝑚𝑚𝑚𝑚𝑚𝑚�𝑃𝑃

𝐹𝐹𝑚𝑚𝑥𝑥 = 𝑚𝑚𝑚𝑚𝑚𝑚 𝑃𝑃𝐷𝐷𝑃𝑃𝐷𝐷(𝑧𝑧()𝑧𝑧𝑚𝑚𝑚𝑚𝑚𝑚)

𝐹𝐹𝑞𝑞 = 𝑃𝑃𝐷𝐷𝑚𝑚𝑚𝑚𝑚𝑚 𝑃𝑃𝐷𝐷

(14)

Results of peaking power factors

Pin-by-pin solver yields non-normal peaking factors, in contrast to the nodal solution.

Peaking factors uncertainty seems very sensitive to spatial meshing.

(15)

Results of peaking power factors

Pin peaking factors

Again, pin peaking power factors show non-normal distributions.

This implies that providing a mean value and a standard deviation is not enough to properly describe the uncertainty.

(16)

Results of peaking power factors

Hottest fuel assembly position in PBP simulations:

• Position A: 77 % of the random samples. • Position B: 23 % of the random samples.

Focusing on the assembly-averaged F∆H obtained using the pin-by-pin solver. F∆H = Normalized power of the hottest fuel assembly.

(17)

SCALE/COBAYA is a suitable tool for UQ at both nodal and pin levels.

It has been applied to Exercise I-3 / TMI-1

Uncertainties in keff

Consistent values between nodal and pin-by-pin simulations (∆k ≈ 500 pcm)

Normally distributed results -> confirms that the mean value and the standard

deviation permit establishing confidence intervals

A large number of simulations mandatory to obtain a mean value in perfect

agreement with the nominal value.

Uncertainties in peaking power factors

The spatial mesh impacts the assembly-averaged peaking factors.

Values computed with the pin solver (both pin- and assembly-averaged) do not

follow a normal distribution -> mean value and the standard deviation are not sufficient and their PDF are mandatory to construct the confidence intervals required for safety analysis.

This behavior highlights the need of performing full core calculations

at the pin-level to get reliable estimates of the uncertainties in peaking factors.

(18)

Thank you for your attention!

This work was supported by the

Spanish Nuclear Safety Council

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